ML18227B260
| ML18227B260 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 03/06/1978 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18227B260 (26) | |
Text
nS/~ S~g REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS>
-,DISTRIBUTION FOR INCOMING MATERIAL 50-250/251 REC:
STELLO V ORG:
UHRIG R E
DOCDATE: 03/06/67 NRC FL PWR 5 LIGHT DATE RCVD: 03/07/78 DOCTYPE:
L'ETTER NOTARIZED:
YES COPIES RECEIVED
SUBJECT:
)
LTR 3 ENCL 0 LICENSEE NOS DPR-31 8c 41 APPL FOR AMEND:
TECH SPECS PROPSED
.CHANGE CONCERNING'NCORPORATING
< ENCL) REVISED K'< Z')
CURVE RE THE 'ECCS REANALYSIS INTO UNITS 3 8c 4 TECH SPECS.
PLANT NAME: TURKEY PT 83 TURKEY PT 83 REVIEWER INITIAL:
XJM DISTR IBUTER INITIAL:
DISTRIBUTION OF THIS 'MATERIAL IS, AS FOLLOWS GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING 'LICENSE.
<DISTRIBUTION CODE A001)
FOR ACTION:
INTERNAL:
EXTERNAL'BR C
W C
.44LTR ONLY(7)
REG FILE4~+LT ONLY(2>
HANAUER44LTR ONLY<'1.)
EISENHUT4wLTR ONLY(.1 BAER44LTR ONLY(1)
GRIMES++LTR ONLY(1)
J.
MCGOUGH+4LTR ONLY< 1)
LPDR S MIAMI'L++LTRONLY(i>
TIC4+LTR ONLY< 1)
NSIC+4LTR ONLY(1)
ACRS CAT B44~LTR ONLY(16)
NRC 'PDR+%LTR ONLY< 1 )
OELD++LTR ONLY(i>
CHECKwwLTR ONLY< 1)
SHAO++LTR ONLY(1>
BUTLER4+LTR ONLY< 1)
J COLLINS++LTR ONLY(i >
DISTRIBUTION:
LTR 40 ENCL 0 SIZE:
1P+iP+10P CONTROL NBR:
780660042 THE END
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.O. BOX 3100 MIAMI,FLORIDA 3310)
IF Director of Nuclear Reactor Regulation Attention:
Mr. Victor Stello, Director Division of Operating Reactors U.S. Nuclear Regulatory Commission FLORIDA POWER 5 LIGHT COMPANY March 6, 1978 L-78-85 Washington, D.C.
20555
Dear Mr. Stello:
8altjMIIIZi'",qI"'(L'~I'~g IIPy Re:
Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 Proposed Amendment to Facility 0 eratin Licenses DPR-31 and DPR-41 On January 27, 1978, Florida Power G Light Company requested an amendment to Turkey Point Units 3 and 4 Facility Operating Licen-ses to authorize operation of the units with up to 19% of the steam generator tubes plugged.
An ECCS reanalysis was submitted in support of this request.
We have subsequently determined that a revised K(Z) curve (Tech-nical Specification Figure 3.2-3) should have been included in our submittal of January 27th.
The revised figure is attached.
We request that. the revised figure be approved for incorporation in the Turkey Point Units 3 and 4 Technical Specifications.
Our vendor has informed us that the ECCS reanalysis which was per-formed to support operation with up to 19% of the steam generator tubes plugged did not include the parameters of three fuel assem-blies, which are presently in the Unit 4 core.
An additional ECCS analysis demonstrated that these 3 assemblies were limiting i.e.
they have an allowable FO less then 2.05 for a portion of the re-mainder of Turkey Point 4 Cycle 4.
Our NSSS vendor has completed analyses which justify operation at full power with the present Unit 4 core configuration.
Results of these analyses and a description of the effect on our License Amendment request dated January 27, 1978 are included in the attach-ment.
This request has been reviewed by the Turkey Point Plant Nuclear Safety Committee and the Florida Power 6 Light Company Nuclear Review Board.
They have concluded that operation in accordance with this requested amendment does not endanger the health and safety of the public.
Yours very truly,
. E. Uhrig Vice President REU/GDW:cs cc:
Mr. J.P. O'Reilly, Region II Robert Lowenstein, Esq.
7'80660042
~0 lb
~]0 HELPING BUILD FLORIDA
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STATE OF FLORIDA
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COUNTY OF DADE
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ss Robert E. Uhrig, being first duly sworn, deposes and says:
That he is a Vice President of Florida Power 6 Light Company, the Licensee herein; That he has executed the foregoing document; that the state-ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.
Robert E. Uhri Subscribed and sworn to before me this day of 19 rZ NOTARY PUBLIC, in and for the County of Dade, State of Florida NOTARY PUSUC STATE OF FI.OIROA st LARGE MY COMIMISSION EXPIRES AUGUST 24, 1%1 My commission expires GGNGED THRU hIAYNARo BGNDM hGQicY
0 ll
ATTACHMENT 1 ECCS analyses performed by Westinghouse, using standard methods reviewed and approved by the NRC as conforming to the requirements of 10CFR50, Appendix K, use as input to part of the calculation an envelope of fuel parameters which covers all Westinghouse fuel manufactured after 1973 and much of'the fuel manufactured before that date.
This envelope of generic fuel parameters was used in calculating the fuel heat up rates and resulting peak clad temperature in the analysis provided to you in January 1978..
A review of that analysis by Fuel Division personnel, after FPL's submittal of the analysis to NRC, revealed that there had been no consideration of three Regi'on 3 fuel assemblies manufactured in 1972 and present in Unit 4, Cycle 4, whose parameters lie outside the generic envelope for some values of peak power density and for some values of fuel burnup.
The presence of this fuel was correctly accounted for in the Westinghouse Reload Safety Evaluation for Cycle 4 in which it was pointed out that Region 3 fuel had a limiting F< of 2.13 compared to the generic fuel limit of 2.22 (enveloping all other fuel in Cycle 4).
For that RSE it was also determined that there was at least 8% margin between the peak calculated on Region 3 fuel and the 2.13 limit.
The new analysis, for 19% steam generator tube plugging requires an F< limit of 2.05 on generic fuel.
Thus for any part of the fuel cycle for which Region 3 has higher calculated pellet average
0 0
Page Two temperatures at the kw/ft corresponding to an F< of 2.05 than the generic fuel curve<
region 3 fuel.parameters determine the P<
limit.
An analysis for Region 3 fuel parameters has been com-pleted which results in an F~ limit of 2.04 for that fuel, until it reaches a minimum cycle burnup of 7400 MWD/T when the limit becomes 2.05, the same as generic fuel.
A supplement to the analysis, already submitted. to the NRC is provided as Attachment 2.
Pollowing the same approach as previously submitted at the beginning of Cycle 4, it has been verified that for the remaining part of the fuel cycle these Region 3 assemblies will meet their LOCA limit, if the remainder.of the core meets the 2.05 LOCA limit, because of the following reasons:
1.
The limiting elevation dependent peak-to-average
- powers, do not, occur in these Region 3 assemblies during Cycle 4
operation.
Xt has been determined from 3-D calculations that at. each elevation the ratio P
Z P
(Z)
< 2.04/2.05 xy is met where P
(Z) and F (Z) are the elevation dependent xy xy radial factors for Region 3 fuel and the other fuel respectively.
2.
The analysis showed about 13% margin to the 2.04 LOCA limit for these Region 3 assemblies using P
(Z) from the 3-D xy calculations.
Page Three Therefore, full power capability based on the F x P 1 envelope of 2.05 x K(Z) is justifiable throughout the remainder of Cycle 4 operation of. Turkey Point Unit 4.
The first two line segments of the F x K(Z) envelope. changes by the ratio of the F~ change;
- however, the third line segment.
does not, change in units of power 'density.
Thus the required function K(Z) is defined by the coordinates
'(1.0, 0 ft.), (1.0, 6 ft.),
( 937 i ll 1 ft ) g
( 488 12 f't )
i+i
FIGURE 2
" Revised 'K(z)- Function for FLA Cycle 4 Burnup
> 5000 MWD/MTU
~
r r
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4 4
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TABLE 2 LARGE BREA!'ECLG BREA!:, C0
= 0.4 RESULTS:
Peak Clad Temperature Peak Clad Location Local Zirc/llater Reaction (max)
Local Zirc/llater Location Total lire/l/ater Reaction Hot Rod Burst Time Hot Rod Burst Location
'.2194
~
F 6.0 12.2 percent 6.0 Ft
<0.3 percent 22 '
scca 6.0 Ft CALCULATrnN Core Pokier (H)l,, 102/. of)
Peak Linear Poiler (Kll/FT, 102".> of)
Peaking Factor (At License Rating)
Accumulator !!ater Volume (FT3) 2200.
11.59 2.04 875 (per accumulator)
FUEL REGION, CYCLE ANALYZED
'UNIT 4 CYCLE 4 REGION 3
1$
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I.4000 1.2500 TURKEY POINT/FPL 0.4 OECLG REOUCEO RCS FLOM MITH ))EM RFO OATA FPL/POMER=2200.0/REG 3
FUEL AT 10184 HMO/HTU BURNUP OUALITY OF FLUIO BURSTl 6.00 FT(
)
PEAKl 6,00 FTIC)
P~ Z 0$
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0.5000 0.2500 0.0 00 Alo0 00 0
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TURKEY POINT/FPL O.O OECLG REOVCED RCS FLOV.VITN NEV NFD OATA FPL/POMER=2200 0/REG 3
FUEL AT 1018c)
HVO/MTU OURNVP MASS VELOCITY 8URST.
6400 FTI
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600.00 SOO.CO 400.00
%0.00 200.00 Cl TURKEY PO?HT/FPL 0.4 DECLC REDUCED RCS FLOV VITH NEVI NFO DATA FPL/POMERP2200.0/RE6 3
FUEL AT 10184 t4VO/NTU &URtlUP ~7 HEAT TRANS ~ COEFFIClENT BURST ~
6 ~ 00 FT(
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PEAK ~
6 ~ 00 Fit4)
T/FPL 0. ~
DECLG REDUCED RCS FLQ" "tI>'EM 't ~ 0 'i< h FPL/POVER~ZPOC.O/REC 3
FUEL hT tG(8 HID/<<FU ".tI<'iJ>
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2000.0 l750.0 LV C
1500.0 TURKEY POINT/FPL 0.4 OECLG REDUCED RCS FLOV VITH NEV NFO DATA FPL/POVER=2200.0/REG 3
FUEL AT IO 184
)RVO/MTU BURNUP FLUID TEMPERATURE BURST.
6.00 FT1
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PEAK 6.00 FT(+)
Fjj It I
1250.0 CC le 1900+0 0
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